• 공업화학
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• 제1권2호
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• pp.240-248
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• 1990

$C_9$ aromatics의 transakylation에 대한 금속담지 H-mordenite의 촉매활성 및 선택도에 관한 실험이 고압의 연속흐름 고정층 반응기에서 수행되었다. 니켈담지 H-mordenite(T-Ni) 촉매는 높은 활성을 나타내었으며, 이 활성의 감소속도가 느렸다. 몰리브덴 및 니켈이 담지된 H-mordenite(T-NiMo) 촉매도 높은 활성을 나타내었으며, 탄화수소의 탄화를 억제하였다. T-Ni 및 T-NiMo 촉매의 선택도는 실험범위 내에서 반응온도가 증가함에 따라 감소하였지만, 상업적으로 사용되는 T촉매의 선택도는 반응온도가 증가함에 따라 서서히 증가하였다. 촉매의 초기활성 및 활성감소 측면에서는 T-Ni 및 T-NiMo 촉매의 성능이 T촉매보다 우수하였으며, 몰리브덴의 첨가는 T-Ni 촉매의 안정성을 다소 개선하였다.

• 한국항공우주학회지
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• 제33권1호
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• pp.69-77
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• 2005

KSR-III 개발과정에서 배플을 장착하여 연소 불안정 현상을 해결한 바 있으나, 추력 및 냉각과 관련된 축방향 길이에 대한 최적화 과정을 거치지는 않았다. 이에 수동제어기구로서 사용되는 배플의 축방향 길이의 최적화 및 한계를 평가하기 위하여, 축방향 길이를 작동인자로 하여 연소 안정성 여분을 평가하였다. 외부 교란 발생 장치로서 2번의 기폭이 가능한 펄스건을 사용하였다. 외부 교란에 대한 연소실에서의 응답 특성을, 감쇠 시간과 진폭비와 같은 인자를 도입하여 정량화하였다. 설계점과 탈설계점에서 시험을 수행하였으며, 분사기의 충돌점으로 생각할 수 있는 화염 영역을 감싸지 못하는 경우에는 배플의 충분한 감쇠 능력을 보장할 수 없음을 확인하였다. 따라서 연소 안정성의 여분의 경계는 KSR-III에서의 작동조건 하에서 50 mm 정도의 배플인 것으로 판단되었다.

• Nuclear Engineering and Technology
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• 제45권5호
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• pp.625-636
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• 2013

Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor 'AHWR' is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI), Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

• Nuclear Engineering and Technology
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• 제28권1호
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• pp.56-71
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• 1996

지지격자를 갖는 5$\times$5 핵연료 봉다발부수로내에서 국부 수력특성인자들을 레이저 유속측정장치인 LDV(Laser Doppler Velocimeter)를 이용하여 측정하였다. 이 연구는 지지격자가 봉다발 난류유동구조에 미치는 영향에 관한 연구에 관점을 두었다. 축방향속도, 난류강도, 편이도, 편평도 등의 측정인자들을 측정하였다. 압력강하를 측정하여 지지격자의 손실계수와 봉다발의 마찰계수를 구하였다 실험결과로부터 활발한 난류혼합거리는 지지격자로부터 x/D$_{h}$=10까지이고, 강제 혼합거리는 지지격자로부터 x/D$_{h}$=20까지임이 관찰되었다. 지지격자하류에서의 축방향 난류강도 감쇄거동은 mesh격자나 screen을 통과하는 난류유동과 같은 경향을 보여주었다. 측정된 자료로부터 부수로해석 code에 입력함수로 적용할 수 있는 국부 난류혼합계수상관식을 구하였다. 국부 혼합계수분포 경향을 관찰하여보면 지지격자 근처에서 최대값을 보이고, 하류방향으로 진행하면서 안정된 값을 갖는다.

• Nuclear Engineering and Technology
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• 제48권6호
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• pp.1321-1329
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• 2016

To get an insight into the operating characteristics of the passive residual heat removal system of molten salt reactors, a two-phase natural circulation test facility was constructed. The system consists of a boiling loop absorbing the heat from the drain tank, a condensing loop consuming the heat, and a steam drum. A steady-state experiment was carried out, in which the thimble temperature ranged from $450^{\circ}C$ to $700^{\circ}C$ and the system pressure was controlled at levels below 150 kPa. When reaching a steady state, the system was operated under saturated conditions. Some important parameters, including heat power, system resistance, and water level in the steam drum and water tank were investigated. The experimental results showed that the natural circulation system is feasible in removing the decay heat, even though some fluctuations may occur in the operation. The uneven temperature distribution in the water tank may be inevitable because convection occurs on the outside of the condensing tube besides boiling with decreasing the decay power. The instabilities in the natural circulation loop are sensitive to heat flux and system resistance rather than the water level in the steam drum and water tank. RELAP5 code shows reasonable results compared with experimental data.

• 한국소음진동공학회논문집
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• 제13권3호
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• pp.217-224
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• 2003

In this study, the adaptive triangular beam method(ATBM) considering different sound reflection coefficients and angles of a triangular beam on two or more planes as well as diffraction effect is suggested. The ATBM, subdividing a tracing triangular beam into multiple triangular beams on reflection planes, gives reliable and convergent sound-field analysis results without the dependancy on the number of initial triangular beam segmentation to search sound propagation paths from source to receiver. The validity of the method is verified by the comparison of numerical and experimental results for energy decay curve and steady-state sound pressure level of rooms having direct, reflective and diffractive sound paths.

• 소음진동
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• 제7권4호
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• pp.579-588
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• 1997

When a membrane couples with compressive fluid, waves on the membrane follow a typical dispersion relations. One of characteristics of this relations is that evanscent waves occur below cutoff frequency. We have attempt to use this spatially decaying characteristics as a low frequency sound absorber. Theoretical development has required to solve membrane-fluid coupled linear differential. The solution has been successfully obtained by using eigenfunctions. To assure the obtained solution, experiment was also performed. The comparison was quite satisfactory. We conclude, based on these theoretical as well as experimental evidences, that it is very likely possible to use a membrane as a low frquency sound control element.

• 한국전기전자재료학회:학술대회논문집
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• 한국전기전자재료학회 1989년도 춘계학술대회 논문집
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• pp.114-117
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• 1989

An infrasonic wide band transducer fabricated by polytetrafluoroethylene(PTFE)is studied experimentally. The sensitivity of the transducer depends largely on the surface charge of the Electret and is typically between-50 and -62[dBV] for a sound-pressure level of 1[ubar]. The sensitivity of the transducer does not decay over periods of the order of years at room temperature. The frequency response is within 1.5[dB] from 1 to 6,000[Hz] and within 12[dB] from 0.05[Hz] to 1[Hz] respectively. The resonance frequency of the element is 510 [Hz]. We conjectures that the element is applicable to accustics, communication system, seismological observation and other similar filed.

• 대한설비공학회지:설비저널
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• 제17권2호
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• pp.131-139
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• 1988

The thermoacoustic oscillation induced in an air column with variable cross section area is investigated theoretically and experimentally. The onset condition of the oscillation is derived by equating the acoustic power production to the power dissipation. The power production at the heater is predicted by using the efficiency factor obtained by heat transfer analysis for a single wire in a uniform cross flow and considering the interference between heater wires. The power dissipation is estimated by measuring the attenuating coefficient from the pressure decay curve. The theoretical prediction to the onset condition of the oscillation is confirmed experimentally. The effect of the variation of the column cross section area on the onset condition is presented.

• Nuclear Engineering and Technology
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• 제38권6호
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• pp.483-488
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• 2006

Highly radioactive waste is placed in metal canisters embedded in dense clay termed buffer. The radioactive decay is associated with heat production, which causes degradation of the buffer and thereby time-dependent loss of its waste-isolating potential. The buffer is prepared by compacting air-dry smectite clay powder and is initially not fully water saturated. The evolution of the buffer starts with slow wetting by uptake of water from the surrounding rock followed by a long period of exposure to heat, pressure from the rock and chemical reactants. It can be described by conceptual and theoretical models describing processes related to temperature (T), hydraulic (H), mechanical (M) and chemical performance (C). For temperatures below 90 C more than 75 % of the smectite will be preserved for 100 000 years but cementation may reduce the excellent performance of the buffer to a yet not known extention.